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	Issue date	Title	Topic
CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc	31 March 2014	Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid	Safe Shutdown Boric Acid Mission time Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Seismically rugged Design basis earthquake Earthquake Seismic Walkdown Report
CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)	11 December 2014	(Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)	Reactor Vessel Water Level Stroke time Anticipated operational occurrence Minimum Critical Power Ratio Fuel cladding Power change
CNL-14-208, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Pl	17 December 2014	Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Plan	Hot Short Safe Shutdown High Radiation Area Mission time Fire Barrier Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Multiple Spurious Operation Incorporated by reference FLEX Thermoset Large early release frequency Severe Accident Management Guideline Fire Protection Program Fire Watch Very Early Warning Fire Detection
CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)	25 September 2015	Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)	Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence MELLLA
CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical	3 June 2015	Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical	Stroke time Fuel cladding
CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report	31 July 2015	the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report	Commercial Grade Dedication
CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision	28 October 2016	Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision
CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report	13 September 2018	Extended Power Uprate - Flow Induced Vibration Summary Report	Flow Induced Vibration
CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report	29 November 2018	Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report
CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions	7 June 2019	Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions	FLEX Design basis earthquake Spent Fuel Pool Instrumentation Severe Accident Management Guideline Hardened vent
CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information	13 March 2019	Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information
CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report	16 April 2019	Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report	Flow Induced Vibration Power Uprate
CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report	4 September 2019	Extended Power Uprate - Flow Induced Vibration Summary Report	Flow Induced Vibration
CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User	16 December 2020	10 CFR 71.95 Report for 3-60B Casks User
CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use	27 May 2022	to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use
CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information	18 July 2022	Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information	Stroke time Anticipated operational occurrence Abnormal operational transient
CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)	9 December 2022	to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)	Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Abnormal operational transient Feedwater Controller Failure MELLLA
ML023040338	19 September 2002	Part 2 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans	Reactor Vessel Water Level Loop seal Hydrostatic Earthquake Fuel cladding Power change Coast down
ML023040361	19 September 2002	Part 4 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans
ML023470308	5 December 2002	Steam Generator Inservice Inspection, Steam Generator Tube Plugging & Repair 30-Day Report	Eddy Current Testing
ML030650716	25 February 2003	Special Report Per Technical Specification 5.6.6., Problem Investigation Process No.: 0-03-0154, 0-03-0415	Post Accident Monitoring
ML032540372	31 May 2003	Pressure-Temperature Curves for TVA Browns Ferry Units 2 and 3	Shutdown Margin Anticipated operational occurrence Hydrostatic Finite Element Analysis
ML032731557	29 September 2003	Technical Letter Report on the Third 10-Year Interval Inservice Inspection Request for Relief Nos. 02-004 and 02-005 for Oconee Nuclear Station, Unit 1	Hydrostatic VT-2 Incorporated by reference Dissimilar Metal Weld
ML041210261	31 January 2003	Tennessee Valley Authority Systems and Analysis Browns Ferry Nuclear Plant Probabilistic Safety Assessment Unit 2 Summary, Revision 1	Internal Flooding Probabilistic Risk Assessment Large early release frequency
ML041550786	29 February 2004	FRA-ANP Document No. 77-5038568-00, LBB Evaluation of the Core Flood and Low Pressure Injection/Decay Heat Removal Piping Systems for Oconee Unit 3.	Safe Shutdown Earthquake Finite Element Analysis Stress corrosion cracking License Renewal Pressure Boundary Leakage Pressure boundary leak Unidentified leakage
ML041840114	30 April 2004	Engineering Report GE-NE-0000-0023-1250-1, Rev 0, Browns Ferry, Units 1, 2 and 3, Steam Dryer Analysis for Extended Power Uprate Conditions.	Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Earthquake Flow Induced Vibration
ML041840116	30 June 2004	Proposed Technical Specifications Change TS-431, Extended Power Uprate UFSAR Review Matrix, Enclosure 6	Safe Shutdown Shutdown Margin Reactor Vessel Water Level Safety Limit Minimum Critical Power Ratio Ultimate heat sink Non-Destructive Examination Stroke time Anticipated operational occurrence Time to boil Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Nondestructive Examination Temporary Modification Finite Element Analysis Significance Determination Process Feedwater Controller Failure Large early release frequency MELLLA Turbine Missile Fuel cladding Fire Protection Program Flow Induced Vibration GOTHIC Power Uprate Failure to Scram
ML041840413	30 April 2004	Engineering Report, Steam Dryer Analysis for Extended Power Uprate Conditions	Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Finite Element Analysis Earthquake Flow Induced Vibration
ML042080336	2 July 2004	Response to Request for Additional Information Related to Technical Specifications Change No. TS-405 Alternative Source Term	Safe Shutdown Ultimate heat sink Grab sample Design basis earthquake Earthquake
ML042380243	31 August 2003	Tennessee Valley Authority System and Analysis Browns Ferry Nuclear Plant, Probabilistic Safety Assessment, Certification and Per Resolution	Safe Shutdown Mission time Finite Element Analysis Large early release frequency Hardened vent
ML042800052	27 May 2004	Zebra Mussels: Biology, Impacts, and Control, Chapter 13	Zebra Mussel
ML042960391	15 October 2004	ORNL/NRC/LTR-04/18, Electronic Archival of the Results of Pressurized Thermal Shock Analyses for Beaver Valley, Oconee, and Palisades Reactor Pressure Vessels Generated with the 04.1 Version of Favor.
ML043380321	15 November 2004	American Society of Mechanical Engineers Section XI, in Service Inspection Program	Probabilistic Risk Assessment Finite Element Analysis Aging Management EVT-1
ML043550271	31 March 2004	CTRS-Report, Thermal - Hydraulic Uncertainty Analysis in Pressurized Thermal Shock Risk Assessment.	Loop seal Probabilistic Risk Assessment Earthquake
ML050560037	8 February 2005	12-5023272-01, Risk Assessment for Alternate STS End States.	Safe Shutdown Boric Acid Shutdown Margin Ultimate heat sink Mission time Time to boil Probabilistic Risk Assessment Offsite Circuit Manual Operator Action
ML050770370	11 March 2005	Technical Specifications (TS) Change TS-447, Request for Additional Information (RAI) - Extension of Channel Calibration Surveillance Requirement Performance Frequency and Allowable Value Revision	Safe Shutdown Earthquake
ML051360155	12 August 1994	IPE-PRA Revision 1, Unit 2.
ML051360162	13 April 1995	IPE-PRA Revision 1A, Unit 2.
ML051640307	22 July 2005	Third 10-Year Interval Inservice Inspection Program Plan Requests for Relief 04-ON-002 and 04-ON-003	Incorporated by reference Liquid penetrant Dissimilar Metal Weld Scaffolding
ML060380671	2 February 2006	Response to NRC Request for Additional Information Regarding Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - Submittal of Browns Ferry Unit 1 Seismic and Internal Fires IPEEE Reports	Hot Short Safe Shutdown High winds Ultimate heat sink Probabilistic Risk Assessment Aging Management Significance Determination Process Design basis earthquake License Renewal Earthquake
ML060620548	27 February 2006	Brown Ferry Nuclear EPU Containment Overpressure (COP) Credit Risk Assessment.
ML060720273	30 November 1992	a Guide for Environmental and Best Management Practices for Tennessee Valley Authority Transmission Construction and Maintenance Activities
ML060720293	28 February 2005	Hydrothermal Modeling of Browns Ferry Nuclear Plant with Units 1, 2, and 3 at Extended Power Uprate	Ultimate heat sink
ML060720354	31 March 2006	GE-NE-0000-0049-6652-01NP, Rev 0, General Electric Boiling Water Reactor Steam Dryer Scale Model Test Based Fluctuating Load Definition Methodology, March 2006 Benchmark Report	Finite Element Analysis Flow Induced Vibration
ML060880464	21 March 2006	BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 1	High winds Mission time Internal Flooding Probabilistic Risk Assessment Coatings Large early release frequency
ML061070632	30 April 2006	Units 1, 2, & 3 - GENE-0000-0052-3661-01-NP, Test Report #1, Browns Ferry Nuclear Plant; Unit 1, Scale Model Test.
ML061300441	31 May 2006	C.D.I. Report 06-11, Rev 1, Hydrodynamic Loads on Browns Ferry, Unit 1 Steam Dryer to 200 Hz.
ML061300443	31 May 2006	GE-NE-0000-0053-7413-R0-NP, Browns Ferry, Units 1, 2 & 3 Steam Dryer Stress, Dynamic and Fatigue Analyses for EPU Conditions.	Finite Element Analysis Earthquake Flow Induced Vibration
ML062090482	10 July 2006	BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 2	High winds Mission time Internal Flooding Probabilistic Risk Assessment Large early release frequency
ML062130343	31 July 2006	C.D.I. Report No. 06-11, Revision 2, Hydrodynamic Loads on Browns Ferry Nuclear Unit 1 Steam Dryer to 200 Hz.

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